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Issue date | Title | |
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ML22090A271 | 31 March 2022 | Constellation Response to Beyond Nuclear and Staff Views in Response to CLI-22-04 |
ML21074A411 | 14 May 2021 | Issuance of Amendment Nos. 338 and 341, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4B |
JAFP-21-0014, Exemption Request to Extend the 10-Year ASME Code Updates for the Inservice Inspection, Containment Inservice Inspection, and Inservice Testing Programs | 3 March 2021 | Exemption Request to Extend the 10-Year ASME Code Updates for the Inservice Inspection, Containment Inservice Inspection, and Inservice Testing Programs |
ML20339A397 | 10 December 2020 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident |
ML19053A469 | 10 June 2019 | Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic |
ML18093B511 | 24 April 2018 | Response to Request for Extension of Seismic Probabilistic Risk Assessment Submittal |
ML16075A329 | 16 March 2016 | OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations |
ML15174A257 | 1 September 2015 | Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14030A046 | 20 February 2014 | Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 |
ML13309A230 | 30 September 2013 | Transcript of 10 CFR Petition Review Board Re(Garding) General Electric Mark I and II (Boiling Water Reactors) Bwrs, 09-30-2013, Pages 1-98(100) |
ML13044A561 | 1 March 2013 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Flooding Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
ML12054A735 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12054A694 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents |
ML12054A679 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12056A044 | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
ML12056A043 | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments |
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments |
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
ML12286A018 | 25 July 2011 | License Amendment Request - Extended Power Uprate, Enclosure 14a to Attachment 14, Setpoint Calculation for Average Power Range Monitor Simulated Thermal Power - High, PE-0251 |
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | 14 July 2011 | G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 |
ML11167A114 | 8 June 2011 | Transcript of 10 CFR 2.206 Petition Review Board Conference Call Re GE Mark 1 Bwrs, June 08, 2011, Pages 1-74 |
ML102140387 | 30 July 2010 | Nuclear Regulatory Commission Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations - Publication Date of August 10, 2010 |
ML082200051 | 9 July 2008 | Comment (2) of David P. Helker, on Behalf of Exelon and Amergen, Concerning Draft Regulatory Guide DG-1195, Availability of Electric Power Sources. |
ML022180220 | 5 August 2002 | 07/23/2002, Summary of License Renewal Meeting Between NRC Staff, Nuclear Energy Inst. (NEI) & Utilities to Discuss Status of License Renewal Activities |
ML031110449 | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
ML20217C414 | 6 October 1999 | Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld |
NRC Generic Letter 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis |
NRC Generic Letter 1998-01 | 14 January 1999 | NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants |
NRC Generic Letter 1998-04 | 14 July 1998 | NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques |
NRC Generic Letter 1997-04 | 30 September 1997 | NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules |
ML20210K367 | 14 August 1997 | Forwards RAI Re ECCS Pump Suction Strainer Mods for Plant, Units 2 & 3 |
ML20148E623 | 27 May 1997 | Forwards Summary of Planned Physical Changes as follow-up to Util 120-day Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions |
NRC Generic Letter 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report |
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents | 24 February 1997 | Implementation of a New Constraint on Radioactive Air Effluents |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks |
NRC Generic Letter 1996-03 | 31 January 1996 | NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits |
NRC Generic Letter 1989-10 | 24 January 1996 | NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors |
NRC Generic Letter 1996-01 | 10 January 1996 | NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits |
NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
NRC Generic Letter 1995-07 | 17 August 1995 | NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves |
NRC Generic Letter 1995-04 | 28 April 1995 | NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues |